ASTM E1893-08

Standard Guide for Selection and Use of Portable Radiological Survey Instruments for Performing In Situ Radiological Assessments to Support Unrestricted Release from Further Regulatory Controls

SIGNIFICANCE AND USE
The purpose of this standard is to provide the user information and guidance for selecting and using instrumentation that will provide measurement results that can be compared to criteria for unrestricted use.
Use of this standard will provide greater assurance that the measurements obtained will be technically and administratively sufficient for making decisions regarding completion of decontamination and/or demolition/removal activities.
Use of this standard will provide greater assurance that the measurements obtained will be technically and administratively sufficient to meet all applicable regulatory requirements for unrestricted release of a component for recycle or reuse, or for unrestricted release of a remaining surface or area.
SCOPE
1.1 This standard provides recommendations on the selection and use of portable instrumentation that is responsive to levels of radiation that are close to natural background. These instruments are employed to detect the presence of residual radioactivity that is at, or below, the criteria for release from further regulatory control of a component to be salvaged or reused, or a surface remaining at the conclusion of decontamination and/or decommissioning.
1.2 The choice of these instruments, their operating characteristics and the protocols by which they are calibrated and used will provide adequate assurance that the measurements of the residual radioactivity meet the requirements established for release from further regulatory control.
1.3 This standard is applicable to the in situ measurement of radioactive emissions that include:
1.3.1 alpha
1.3.2 beta (electrons)
1.3.3 gamma
1.3.4 characteristic x-rays
1.3.5 The measurement of neutron emissions is not included as part of this standard.
1.4 This standard dose not address instrumentation used to assess residual radioactivity levels contained in air samples, surface contamination smears, bulk material removals, or half/whole body personnel monitors.
1.5 This standard does not address records retention requirements for calibration, maintenance, etc. as these topics are considered in several of the referenced documents.

General Information

• Status: Historical
• Publication Date: 31-May-2008
• ICS: 17.240 - Radiation measurements
• Technical Committee: E10 - Nuclear Technology and Applications
• Drafting Committee: E10.03 - Radiological Protection for Decontamination and Decommissioning of Nuclear Facilities and Components

Relations

• Replaces: ASTM E1893-97(2003) - Standard Guide for Selection and Use of Portable Radiological Survey Instruments for Performing In Situ Radiological Assessments in Support of Decommissioning
• Effective Date: 01-Jun-2008
• Replaced By: ASTM E1893-08a - Standard Guide for Selection and Use of Portable Radiological Survey Instruments for Performing In Situ Radiological Assessments to Support Unrestricted Release from Further Regulatory Controls
• Effective Date: 01-Nov-2008
• Referred By: ASTM E2420-15(2021) - Standard Guide for Post-Deactivation Surveillance and Maintenance of Radiologically Contaminated Facilities
• Effective Date: 01-Jun-2008
• Referred By: ASTM E1760-16 - Standard Guide for Unrestricted Disposition of Bulk Materials Containing Residual Amounts of Radioactivity
• Effective Date: 01-Jun-2008
• Referred By: ASTM E2216-02(2020) - Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning
• Effective Date: 01-Jun-2008
• Referred By: ASTM E1167-15(2021) - Standard Guide for Radiation Protection Program for Decommissioning Operations
• Effective Date: 01-Jun-2008
• Referred By: ASTM E1281-15(2021) - Standard Guide for Nuclear Facility Decommissioning Plans
• Effective Date: 01-Jun-2008

Standards Content (Sample)

NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information
Designation:E 1893–08
Standard Guide for
Selection and Use of Portable Radiological Survey
Instruments for Performing In Situ Radiological
Assessments to Support Unrestricted Release from Further
1
Regulatory Controls
This standard is issued under the fixed designation E 1893; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope 2. Referenced Documents
2
1.1 This standard provides recommendations on the selec- 2.1 ASTM Standards:
tion and use of portable instrumentation that is responsive to C 998 Practice for Sampling Surface Soil for Radionuclides
levels of radiation that are close to natural background. These C 999 Practice for Soil Sample Preparation for the Deter-
instruments are employed to detect the presence of residual mination of Radionuclides
radioactivity that is at, or below, the criteria for release from C 1000 Test Method for Radiochemical Determination of
further regulatory control of a component to be salvaged or Uranium Isotopes in Soil by Alpha Spectrometry
reused, or a surface remaining at the conclusion of decontami- C 1133 Test Method for Nondestructive Assay of Special
nation and/or decommissioning. Nuclear Material in Low-Density Scrap and Waste by
1.2 The choice of these instruments, their operating charac- Segmented Passive Gamma-Ray Scanning
teristics and the protocols by which they are calibrated and E 170 Terminology Relating to Radiation Measurements
used will provide adequate assurance that the measurements of and Dosimetry
the residual radioactivity meet the requirements established for E 181 Test Methods for Detector Calibration and Analysis
release from further regulatory control. of Radionuclides
1.3 This standard is applicable to the in situ measurement of C 1215 Guide for Preparing and Interpreting Precision and
radioactive emissions that include: Bias Statements in Test Method Standards Used in the
1.3.1 alpha Nuclear Industry
1.3.2 beta (electrons) 2.2 ANSI Standards:
1.3.3 gamma ANSIN323B RadiationProtectionInstrumentationTestand
1.3.4 characteristic x-rays Calibration, Portable Survey Instrumentation for Near
3
1.3.5 Themeasurementofneutronemissionsisnotincluded Background Operation
as part of this standard. ANSI N42.17A Performance Specifications for Health
1.4 This standard dose not address instrumentation used to Physics Instrumentation-Portable Instrumentation for Use
3
assess residual radioactivity levels contained in air samples, in Normal Environmental Conditions
surface contamination smears, bulk material removals, or ANSI N42.17C Performance Specifications for Health
half/whole body personnel monitors. Physics Instrumentation-Portable Instrumentation for Use
3
1.5 Thisstandarddoesnotaddressrecordsretentionrequire- in Extreme Environmental Conditions
ments for calibration, maintenance, etc. as these topics are 2.3 National Council on Radiation Protection and Mea-
considered in several of the referenced documents. surements:
NCRP Report No. 57 Instrumentation and Monitoring
1 2
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Technology and Applications and is the direct responsibility of Subcommittee contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
E10.03 on Radiological Protection for Decontamination and Decommissioning of Standards volume information, refer to the standard’s Document Summary page on
Nuclear Facilities and Components. the ASTM website.
3 th
CurrenteditionapprovedJune1,2008.PublishedJuly2008.Originallyapproved American National Standards Institute, 11 W. 42nd St., 13 Floor, New York,
in 1997. Last previous edition approved in 2003 as E 1893-97(2003). NY 10036
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
1

---------------------- Page: 1 ----------------------
E 1893–08
Methods for Radiation Protection, National Council on some of its chemical or physical or radiological properties, and
4
Radiation Protection and Measurements, May 1978 that is generally used for calibration of a measurement system
NCRP Report No. 58 A Handbook of Radioactivity Mea-
or for development or evaluation of a measurement method
surement Procedures, National Council on Radiation Pro- (ASTM E 170).
4
tection and Measurements, 2nd Ed. February 1985
3.5 check source, n—a radioactive source, not necessarily
NCRP Report No. 112 Calibration of Survey Instruments
calibrated, which is used to confirm the continuing satisfactory
Used in Radiation Protection for the Assessment
...

This document is not anASTM standard and is intended only to provide the user of anASTM standard an indication of what changes have been made to the previous version. Because
it may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current version
of the standard as published by ASTM is to be considered the official document.
Designation:E 1893–97 (Reapproved 2003) Designation:E 1893–08
Standard Guide for
Selection and Use of Portable Radiological Survey
Instruments for Performing In Situ Radiological
Assessments in Support of DecommissioningSelection and
Use of Portable Radiological Survey Instruments for
Performing In Situ Radiological Assessments to Support
1
Unrestricted Release from Further Regulatory Controls
This standard is issued under the fixed designation E 1893; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope
1.1 This standard provides recommendations on the selection and use of portable instrumentation that is responsive to levels
of radiation that are close to natural background. These instruments are employed to detect the presence of residual radioactivity
that is at, or below, the criteria for release from further regulatory control of a component to be salvaged or reused, or a surface
remaining at the conclusion of decontamination and/or decommissioning.
1.2 The choice of these instruments, their operating characteristics and the protocols by which they are calibrated and used will
provide adequate assurance that the measurements of the residual radioactivity meet the requirements established for release from
further regulatory control.
1.3 This standard is applicable to the in situ measurement of radioactive emissions that include:
1.3.1 alpha
1.3.2 beta (electrons)
1.3.3 gamma
1.3.4 characteristic x-rays
1.3.5 The measurement of neutron emissions is not included as part of this standard.
1.4 This standard dose not address instrumentation used to assess residual radioactivity levels contained in air samples, surface
contamination smears, bulk material removals, or half/whole body personnel monitors.
1.5 This standard does not address records retention requirements for calibration, maintenance, etc. as these topics are
considered in several of the referenced documents.
2. Referenced Documents
2
2.1 ASTM Standards:
C 998 Practice for Sampling Surface Soil for Radionuclides
C 999 Practice for Soil Sample Preparation for the Determination of Radionuclides
C 1000 Test Method for Radiochemical Determination of Uranium Isotopes in Soil by Alpha Spectrometry
C 1133 Test Method for Nondestructive Assay of Special Nuclear Material in Low-Density Scrap and Waste by Segmented
Passive Gamma-Ray Scanning
E170Standard Terminology Relating to Radiation Measurements and Dosimetry 170 Terminology Relating to Radiation
Measurements and Dosimetry
E 181Standard General Test Methods for Detector Calibration and Analysis of Radionuclides
C 1215Standard Guide Guide for Preparing and Interpreting Precision and Bias Statements in Test Method Standards Used in
the Nuclear Industry
2.2 ANSI Standards:
ANSI N323Radiation Protection Instrumentation Test and Calibration
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear Technology and Applications and is the direct responsibility of Subcommittee E10.03 on
Radiological Protection for Decontamination and Decommissioning of Nuclear Facilities and Components.
Current edition approved June 10, 1997. Published March 1998.
Current edition approved June 1, 2008. Published July 2008. Originally approved in 1997. Last previous edition approved in 2003 as E 1893-97(2003).
2
For referencedASTM standards, visit theASTM website, www.astm.org, or contactASTM Customer Service at [e-mail]. For Annual Book of ASTM Standards
, Vol 12.02.volume information, refer to the standard’s Document Summary page on the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
1

---------------------- Page: 1 ----------------------
E 1893–08
4
ANSI N15.5Statistical Terminology and Notation for Nuclear Materials Management ANSI N323B Radiation Protection
3
Instrumentation Test and Calibration, Portable Survey Instrumentation for Near Background Operation
ANSI N42.17A Performance Specifications for Health Physics Instrumentation-Portable Instrumentation for Use in Normal
3
Environmental Conditions
ANSI N42.17CPerformance Specifications for Health Physics Instrumentation-Portable Instrumentation for Use in Extreme
4
Environmental Conditions
4
ANSI N42.3Standard Test Procedure for Geiger Mueller Counters ANSI N42.17C Performance Spec
...